OOIR: Observatory of International Research

Papers

(The median citation count of Science and Technology of Nuclear Installations is 1. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2022-06-01 to 2026-06-01.)

Article	Citations
Investigation of Oxidation and Counter-Oxidation in a One-Quarter Circular Geometry due to Shadow Corrosion	31
Vacuum Analysis and Experiment of Free‐Electron Laser Oscillator Based on Molflow+ Simulation	15
Effect of Inhomogeneous Mechanical Properties on the Stress-Strain Field at the Crack Tip and Crack Growth Direction in Dissimilar Metal Welded Joints	11
Implications of Innovative Nuclear Technologies on Ghana’s Nuclear Future	10
Cold Atmospheric Plasma Inhibits the Proliferation of CAL-62 Cells through the ROS-Mediated PI3K/Akt/mTOR Signaling Pathway	10
An Information Granulated Based SVM Approach for Anomaly Detection of Main Transformers in Nuclear Power Plants	10
Investigation of Early Corrosion Behavior of Canister Candidate Materials in Oxic Groundwater by the EQCM Method	8
Research on Optimization of Roof Shielding Design for Radioactive Waste Temporary Storage Facilities	8
Study on Fuel Rod Melting and Molten Material Migration in Core Channels Based on Particle Method	8
The Design and Analysis of Active–Passive Hybrid Vibration Isolation Mounts Applied in Pump	7
Development of an Integrated Human Error Simulation Model in Nuclear Power Plant Decommissioning Activities	7
	7
Evaluation of Improved Contribution Function Method in the Compression of CINDER90 Depletion Library	7
Improvement of the Power Supply Technical Scheme for the Electric Melter System in High‐Level Radioactive Liquid Waste Vitrification	5
Nuclear Waste Management: A Mini Review on Waste Package Characterization Approaches	5
Prediction of Crack Propagation Directions in Dissimilar Metal‐Welded Joints Using Phase‐Field Models and Discussion of Its Mechanisms	4
Optimization of the n / γ Pulse Shape Discrimination Performance of Plastic Scintillator Coupled With SiPM	4
A Data-Driven Fault Prediction Method for Nuclear Power Systems Based on End-to-End Deep Learning Framework	4
Correction to “Count Loss Evaluation for Accuracy Enhancement of a FPGA‐Based Gamma Spectroscopy”	4
Evaluation of Worker Radiation Exposure during the Kori Unit 1 Steam Generator Dismantling Process	4
Time‐Series Forecasting of a Typical PWR Undergoing Large Break LOCA	4
ELSMOR European Project: Experimental Results on an Innovative Decay Heat Removal System Based on a Plate-Type Heat Exchanger	4
Detecting Unauthorized Movement of Radioactive Material Packages in Transport with an Adam-Optimized BP Neural Network Model	4
Enhancing Radiation Shielding with Gadolinium(III) Oxide in Cerium(III) Fluoride‐Doped Silica Borate Glass	3
Exponential Response Matrix Spectral Nodal Method for the Discrete Ordinates Neutral Particle Transport Model	3

The Study of Dosimetric Characteristics of the XHA600D Medical Linear Accelerator Based on a Monte Carlo Code	3
Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material	3
An Improved Steady-State and Transient Analysis of the RSG-GAS Reactor Core under RIA Conditions Using MTR-DYN and EUREKA-2/RR Codes	3
Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-Cooled Fast Reactor: Review of Experimental and Modeling Investigations	3
Effect of Chloride Ions on Electrochemical Behavior of Canister Materials	3
Research on Radionuclide Diffusion Mechanism in the Ocean and Emergency Response under Oceanic Radioactive Events	3
Prediction of Automatic Scram during Abnormal Conditions of Nuclear Power Plants Based on Long Short-Term Memory (LSTM) and Dropout	3
Assessment of Computational Technicalities for 2D/1D Coupling Method and Its Comparison with 3D MOC	3
A Hybrid Method to Predict the Remaining Useful Life of Scroll Wheel of Control Rod Drive Mechanism	3
Accuracy Evaluation of Monte Carlo Simulation Results Using ENDF/B‐VIII.0 and JENDL‐5 Libraries for 10 MW_th Micro Heat Pipe‐Cooled Reactor	3
Accident Sequence Precursor Analysis of an Incident in a Japanese Nuclear Power Plant Based on Dynamic Probabilistic Risk Assessment	3
Methods for Predicting the Minimum Temperature of the Outage Loop and the Maximum Power Caused by the Low-Temperature Coolant	2
A Systematic Framework for Risk Assessment of Fusion Blanket: Addressing Manufacturing Defects, Accident Scenarios, and Radioactive Release	2
Coincidence Summing Factor Calculation for Volumetric γ-ray Sources Using Geant4 Simulation	2
Quantitative Assessment of Gaseous Effluents during Routine Operation: A Comparative Study of Planned Nuclear Power Plants at Lubiatowo‐Kopalino and Pątnów Sites in Poland	2
Analysis of the Effect of Applied Load on Crevice Corrosion Behavior	2
Machine Learning-Based Approach for Hydrogen Economic Evaluation of Small Modular Reactors	2
CFD‐Assisted Spray Decontamination Process Assessment for Nuclear Tank Decommissioning	2
Natural Convection Heat Transfer Analysis With Different DHX Operation Conditions of Sodium‐Cooled Fast Reactor Using ATHLET Code	2
Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel	2
High-Temperature Corrosion Behavior of Incoloy 800H Alloy in the Impure Helium Environment	2
Assessing the Impact of Common Cause Failures on Site Risk within Level 1 Multi-Unit PSA	2
Acceptable Level of Acceptance and the Affecting Factors: What Is the Acceptable Public Acceptance of Building a Nuclear Power Plant	1
Pressurized Water Reactor Transient Detection With Artificial Intelligence to Support Reactor Operators	1
A Reduced Order Model Based on ANN-POD Algorithm for Steady-State Neutronics and Thermal-Hydraulics Coupling Problem	1
Application of EDG AOT Extension Based on the Risk-Informed Method in NPPs	1
Transmuting the Arid: Fission‐Powered Visions—Unlocking Ghana’s Aquatic Destiny Through Nuclear Desalination	1
	1
Analysis With Different Containment Models for Containment Response of NHR200II Under Loss‐of‐Coolant Accident	1
Nuclear Power Sustainability Path for China from the Perspective of Operations	1
Experimental Study on Unsteady Radon Exhalation from the Overburden Layer of the Uranium Mill Tailings Pond under Rainfall	1
Alternate Method for Calibration of PRDs by Means of Gamma Radiation Emitted by Radionuclides	1
Design Change and Operational Consideration of the HVAC System during Nuclear Power Plant Decommissioning	1
Deep Learning–Based Fault Identification Testing Experiment for Bellows Valves	1
Numerical Simulation of UF ₄ Erosion Behaviors in Fluorination Furnace	1
Uranium Recovery from Phosphates for Self-Sufficient Nuclear Power in the Eastern Mediterranean	1
Study on the Dispersion of Radionuclides under Different Hydrological Conditions of Spent Fuel Shipping in Daya Bay	1